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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses c… more
Date: January 1964
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle

Description: Summary: An EVESR MKI prototype fuel bundle was fully instrumented and operated intermittently for a 5-month period at the Pacific Gas and Electric Company’s Moss Landing Power Station. The vessel was operated up to 1000 psi with steam flows from 3000 to 26,600 lb/h, and steam inlet temperatures up to 825 degrees F. Data was recorded for blowout, vibration, flow distribution, heat transfer and pressure drop. The mechanical integrity of the fuel bundle, riser, and jumper system was satisfact… more
Date: February 1964
Creator: Polomik, E. E.; Fritz, J. R. & Ianni, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Description: Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are … more
Date: February 1964
Creator: Case, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

Description: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AEC Fuel Cycle Program Design and Fabrication of Special Assembly 9-L : Irradiation Performance Test of UO2-Cermet Fuel

Description: Technical report describing a UO2-Mo cermet fuel assembly fabricated for long-term irradiation performance testing in the Vallecitos Boiling water Reactor. The design and fabrication histories of this assembly are described and pre-irradiation data on each individual rod are presented. Molybdenum was added to improve the bulk thermal conductivity of the fuel, so that fuel temperatures would remain comparatively low during high-power level operation of the fuel element. The molybdenum was inc… more
Date: March 1964
Creator: Ogawa, S. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Mass Transfer. [Part] XI. 1963 Test Run Reports (January - June)

Description: Technical report describing how corrosion data and exposure effects were obtained by subjecting metallic samples, during programmed test runs to flowing sodium in 6 test loops fabricated with various combinations of three selected materials, Type 316 stainless steel, 2 1/4 Cr-1 Mo alloy steel, and 5 Cr-1/2 Mo-1/2 Ti alloy steel. Information produced by each test run, including operational and metallurgical data and analyses, is presented. Data are shown in tables, graphs, and drawings.
Date: February 1964
Creator: Lockhart, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Design of the Mixed Spectrum Critical Assembly

Description: Summary: The Mixed Spectrum Superheater (MSSR) is an integral superheater reactor in which boiling occurs in an annular Boiling Water Reactor section and steam in superheated in an unmoderated fast section in the center. A Mixed Spectrum Critical Assembly (MSCA) to be operated at the Vallecitos Atomic Laboratory has been designed to mock up a 75-150 MWe prototype MSSR. The principal experimental measurements aimed at proving the feasibility of the MSSR concept include power distribution, Dopple… more
Date: August 1963
Creator: Reynolds, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Fourteenth Quarterly Progress Report, July-September 1963

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development. The number of assemblies has been reduced to seven as a result of the failure of two pellet fuel assemblies. The average burnup of the group operating as of September 1 is 7500 MWD/T. (2) Task 1B-Fuel Fabrication Development. Assembly. Assembly 12S gave positiv… more
Date: October 1963
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program Design and Fabrication of Special Assembly 10-L : Compacted Powder Fuel Rods Clad With 0.127-MM Wall Stainless Steel

Description: Technical report describing sixteen fuel rods clad with thin type 304 stainless steel and filled with vibratory compact powder UO2 that were fabricated and incorporated into a bundle for irradiation testing in the VBWR. The UO2 powders were tested for gas content. N2, CO, and H2 were the principal gases evolved by both type of UO2, but the arc-fused UO2 released about ten times as much gas as the Dyna Pak UO2. The amount of gas released was also a function of particle size and temperature. The… more
Date: October 1963
Creator: Ogawa, S. Y. & Williamson, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prediction of Two-Phase Critical Flow Rate

Description: Technical report of a proposal of an analytical model to predict two-phase critical flow rate. The model is based upon thermal equilibrium, a "lumped" treatment of the two-phase velocity (each phase is represented by a single mean velocity), and upon the neglect of frictional and hydrostatic pressure losses. A comparison, of the proposed predictions with available test results and previous analyses shows that: (1) The present model agrees very well with the published test data. (2) In contrast … more
Date: October 1963
Creator: Levy, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Fabrication of Pellet Fuel Rods Clad With Thin Wall Stainless Steel

Description: Summary: Stainless steel clad nuclear fuel cycle costs can be reduced to those associated with Zircaloy clad fuel or potentially lower by reducing the thickness of the clad tube wall until performance penalties offset the savings associated with the reduction in parasitic neutron absorption. To demonstrate the feasibility and investigate performance capabilities of thin clad fuel rods for power reactor application an assembly was fabricated with 0.0127 cm (5 mil) thick stainless steel cladding … more
Date: February 1964
Creator: Hoffmann, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Heat Transfer to Superheated Steam

Description: Abstract: The physical property variation of superheated steam differs sufficiently from most other gases to warrant experimental investigation of heat transfer performance. Results are reported here of measurements made in a uniformly heated circular duct with steam at 1000 psi. The data agree very well with the expression use for design purposes, which is based on information in the literature for heating of other gases as well as steam. This work was a continuation of that performed under … more
Date: May 1963
Creator: Sutherland, W. A. (William Alan), 1931-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Chemical Engineering of the Radium Process : Final Report

Description: Radium which occurs with the uranium in pitchblende ores remains with the gangue when the uranium is extracted by a hot, mixed acid leach. Upon completion of the laboratory research on the radium process, this report was organized into three phases which are contained in this publication.
Date: unknown
Creator: Hawlings, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Fabrication of Fuel Rods Containing Sintered UO2 Extrusions - Assembly 11L

Description: The extrusion forming of ceramic powders may be economically interesting in the field of nuclear fuel fabrication. When applied to the forming of rod-type uranium dioxide fuel, extrusion processes have been able to produce cylindrical bodies with length-to-diameter ratios much greater than those of the conventional die-pressed pellets. Furthermore, after being sintered, the extrusions have exhibited densities at least as high as those of sintered pellets. Thus, extrusion forming may offer re… more
Date: February 1964
Creator: Megerth, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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